Browse wiki

SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

Boron +, Nitrogen +, Oxygen +  and Hydrogen +

BSEP 94-0316 +, BSEP 94-0179 +, BSEP 95-0535 +, BSEP 96-0123 +, BSEP 95-0572 +, BSEP 96-0340 +, BSEP 96-0300 +, BSEP 96-0287 +, BSEP 96-0242 +, BSEP 96-0348 +, BSEP 96-0362 +, BSEP 96-0392 +, BSEP 96-0403 +  and BSEP 96-0412 +

10 CFR 50 Appendix R +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +  and 10 CFR 51.21 +

BSEP 94-0316 +, BSEP 94-0179 +, BSEP 95-0535 +, BSEP 96-0123 +, BSEP 95-0572 +, BSEP 96-0340 +, BSEP 96-0300 +, BSEP 96-0287 +, BSEP 96-0242 +, BSEP 96-0348 +, NLS-92-180 +, BSEP 96-0362 +, BSEP 96-0392 +, BSEP 96-0403 +  and BSEP 96-0412 +

05000324  +, 05000325  +, 00325  +  and 00324  +

Turbine Trip +  and Reactor Trip +

61 FR 25698 +  and 61 FR 55673 +

SIL 377 +  and SIL 480 +

GDC 17, Electric power systems +  and GDC 19, Control room +

NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +, ML20134F692 +  and ML20134F692 +

2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

10 CFR 2 +, ML20079E131 +, ML20099B295 +, BSEP-95-0572, Provides Response to Parts 2,3 & 4 of GL 92-01,Rev 1,Suppl 1,which Requests Licensee to Identify,Collect & Rept Any New Data Pertinent to Analysis of Structural Integrity & to Assess Impact of Data on RPV Integrity Analyses +, BSEP-94-0316, Forwards Reactor Vessel Matl Surveillance Specimen Test Results,Per 10CFR50,App H +, Power Uprate +, 05000324/LER-1992-003, :on 920413,observed That Foundation Bolts on Control Bldg Emergency Air Filtration Unit Appeared Not to Be in Full Contact W/Nuts.Caused by Missing Clip Angle Weld. Bolts Repaired & Welds Fabricated at Angle +  and 05000325/LER-1994-007, :on 940418,meter Lead Inadvertently Touched Adjacent Terminal Resulting in RCIC Inboard Steam Valve Closure.Caused by Personnel Error.Corrective Action:Meetings Were Held & self-assessments in Progress +

NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

RT +  and Emergency Operating Procedure +

ML20134F692 +, ML20134F692 +  and ML20134F692 +

Regulatory Guide 1.139 +  and Regulatory Guide 1.7 +

NEDC-31624P +, NEDC-31897P +, NEDC-31984P +  and NEDC-32466P +

Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Stator Cooling Water +, Residual Heat Removal Service Water +, Stator Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Low Pressure Coolant Injection +...

Safe Shutdown +, Reactor Vessel Water Level +, Safety Limit Minimum Critical Power Ratio +, Ultimate heat sink +, Temporary Modification +, High Energy Line Break +, Flow Accelerated Corrosion +, Feedwater Heater +, Feedwater Controller Failure +, Turbine Missile +, Fuel cladding +, Power Uprate +, Overspeed trip +, Overspeed +, Simmer margin +, Subsequent actuation +  and Control Room Habitability +